Scholarworks@UNIST

UNIST Library

Browsing by Keyword : PWR

All A B C D E F G H I J K L M N O P Q R S T U V W X Y Z

가 나 다 라 마 바 사 아 자 차 카 타 파 하

Sort by: In order: Results/Page Etal:

Showing results 1 to 15 of 15

Analysis of Rostov-II Benchmark Using Conventional Two-Step Code Systems File

Jang, Jaerim , Hursin, Mathieu , Lee, Woonghee , Pautz, Andreas , Papadionysiou, Marianna , Ferroukhi, Hakim , Lee, Deokjung

Article Issue Date2022-05 View92

Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS File File

Setiawan, Fathurrahman , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2021-01 View119

Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operation File

Jang, Jaerim , Choe, Jiwon , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung , Shin, Ho Cheol

Article Issue Date2020-06 View103

Cooldown procedure success criteria map for the full break size spectrum of SBLOCA File

Fynan, Douglas A. , Cho, Jaehyun , Ahn, Kwang-Il

Article Issue Date2018-01 View103

Development and validation of transient analysis module in nodal diffusion code RAST-V with Kalinin-3 coolant transient benchmark File File

Jang, Jaerim , Lee, Deokjung

Article Issue Date2024-06 View107

Development of nodal diffusion code RAST-V for Vodo-Vodyanoi Energetichesky reactor analysis File File

Jang, Jaerim , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2022-09 View97

Effect of heat flux on the structural and chemical characteristics of fuel CRUD under pressurized water reactor primary water conditions File

Lee, Yunju , Ham, Junhyuk , Yoo, Seung Chang , Song, Inyoung , Jeong, Junhyuk , Kim, Ji Hyun

Article Issue Date2025-08 View112

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing File

Lee, Tae Hyun , Ryu, Kyung Ha , Kim, Hong Deok , Hwang, Il Soon , Kim, Ji Hyun , Lee, Min Ho , Choi, Sungyeol

Article Issue Date2019-08 View122

Machine learning of LWR spent nuclear fuel assembly decay heat measurements File File

Ebiwonjumi, Bamidele , Cherezov, Alexey , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2021-11 View99

The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation File File

Kim, Ji Yong , Lee, Yunju , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2023-09 View109

Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with STREAM/RAST-K File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-08 View113

Uncertainty Analysis of UAM TMI-1 Benchmark by STREAM/RAST-K File File

Jang, Jaerim , Jo, Yunki , Lee, Deokjung

Article Issue Date2024-05 View143

Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parameters File File

Ebiwonjumi, Bamidele , Kong, Chidong , Zhang, Peng , Cherezov, Alexey , Lee, Deokjung

Article Issue Date2021-03 View121

Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K File File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Cherezov, Alexey , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-09 View93

Verification and validation of isotope inventory prediction for back-end cycle management using two-step method File File

Jang, Jaerim , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Cherezov, Alexey , Park, Jinsu , Lee, Deokjung

Article Issue Date2021-07 View97

RSS 1.0 RSS 2.0

UNIST | Library

Tel : 052-217-1403 / Email : scholarworks@unist.ac.kr

ScholarWorks@UNIST was established as an OAK Project for the National Library of Korea.